Fast Reactors and Accelerator Driven Systems Knowledge Base

IAEA-TECDOC--1039: Influence of high dose irradiation on core structural and fuel materials in advanced reactors

Influence of high dose irradiation on core structural and fuel materials in advanced reactors. Technical committee meeting, Obninsk (Russian Federation), 16-19 Jun 1997

International Atomic Energy Agency, Vienna (Austria), IAEA-TECDOC--1039

Abstract

The IAEA International Working Group on Fast Reactors (IWGFR) periodically organizes meeting to discuss and review important aspects of fast reactor technology. The fifth meeting held in Obninsk, Russian Federation, 16-19 June 1997, was devoted to the influence of high dose irradiation on the mechanical properties of reactor core structural and fuel materials. The proceedings includes the papers submitted at this meeting each with a separate abstract

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Articles

Current status of studies on FR fuel and structural materials in the Russian Federation
Poplavsky, V.M.;Zabudko, L.M. (Institute of Physics and Power Engineering, Obninsk (Russian Federation))

Neutron irradiation effects in fusion or spallation structural materials: Some recent insights related to neutron spectra
Garner, F.A.;Greenwood, L.R. (Pacific Northwest National Lab., Richland, WA (United States))

Status and possibility of fuel and structural materials experimental irradiation in BN-600 reactor. Stages of BN-600 reactor core development
Vasiljev, B.A.;Zinovjev, A.I.;Staroverov, A.I. (Experimental Machine Building Bureau, Nizhny Novgorod (Russian Federation));Maltsev, V.V.;Ogorodov, A.N. (NPP BN-600, Zarechny (Russian Federation))

Performance of FBTR mixed carbide fuel
Govindarajan, S.;Puthiyavinayagam, P.;Clement Ravi Chandar, S.;Chetal, S.C.;Bhoje, S.B. (Indira Gandhi Centre for Atomic Research, Kalpakkam (India))

Post-irradiation examination of mixed (Pu, U)C fuels irradiated in the fast breeder reactor
Baldev, R.;Kasiviswanathan, K.V.;Venugopal, V. (Metallurgy and Materials Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)) (and others)

Development of vibropac MOX fuel pins serviceable up TP superhigh burnups
Mayorshin, A.A.;Gadzhiev, G.I.;Kisly, V.A.;Skiba, O.V.;Tzykanov, V.A. (Research Institute of Atomic Reactors, Dimitrovgrad (Russian Federation))

Assemblies and fuel pin behaviour under irradiation in FBR-350
Karaulov, V.N.;Blynski, A.P.;Yakovlev, I.L.;Kononova, E.V. (Mangyshlak Atomic Energy Complex, Aktau (Kazakhstan))

In-pile tests and post-reactor investigations of fuel pins with U-Pu Fuel
Moseev, L.I.;Vorobyev, A.N.;Zabudko, L.M.;Kiryanov, B.S.;Porollo, S.I.;Shulepin, S.V. (State Scientific Center, Institute of Physics and Power Engineering, Obninsk (Russian Federation));Antipov, S.A.;Menshikova, T.S. (Institute of Inorganic Materials, Moscow (Russian Federation))

Inner wall attack and its inhibition method for FBR fuel pin cladding at high burnup
Xu Yongli;Long Bin;Li Jingang;Wan Jiaying (China Inst. of Atomic Energy, Beijing (China))

Material properties of a high-dose irradiated martensitic wrapper: Steel 1.4914
Materna-Morris, E.;Ehrlich, K (Forschungszentrum Karlsruhe, Institut für Materialforschung, Karlsruhe (Germany))

The performance of type EP-450 ferritic-martensitic steel under neutron irradiation at low temperatures
Khabarov, V.S.;Dvoriashin, A.M.;Porollo, S.I. (Institute of Physics and Power Engineering, State Scientific Center, Obninsk (Russian Federation))

Post-irradiation examination of Ti or Nb stabilized austenitic steels irradiated as BN-600 reactor fuel pin claddings up to 87 dpa
Porollo, S.I.;Vorobyev, A.N.;Shulepin, S.V. (Institute of Physics and Power Engineering, State Scientific Center, Obninsk (Russian Federation))

Influence of swelling and creep data on PFBR core design
Puthiyavinayagam, P.;Gopal, S.;Winston, S.J.;Govindarajan, S.;Chetal, S.C.;Bhoje, S.B. (Reactor Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India))

Development of martensitic steels for high neutron damage applications
Gelles, D.S. (Battelle Pacific Northwest National Lab., Richland, WA (United States))

Irradiation creep of austenitic steels irradiated up to high fluence in the BOR-60 reactor
Neustroev, V.S.;Shamardin, V.K. (SSC RF Research Institute of Atomic Reactors, Dimitrovgrad (Russian Federation))

Influence of high dose irradiation on structure and fracture of the C0.1-Cr16-Ni15-Mo3-Nb steel
Averin, S.A.;Kozlov, A.V.;Shcherbakov, E.N. (Research and Development Inst. of Power Engineering, Sverdlovsk Branch, Zarechny (Russian Federation))

Variability of irradiation creep and swelling of HT9 irradiated to high neutron fluence at 400-600 deg.C
Toloczko, M.B.;Garner, F.A. (Pacific Northwest National Lab., Richland, WA (United States))

A problem to determine short term mechanical properties changes of ferrite-martensite and austenitic steels as materials of fuel assembly of fast reactors under high dose neutron irradiation
Kozolov, A.V.;Averin, A.S.;Brushkova, S.V. (Research and Development Inst. of Power Engineering, Zarechny, Sverdlovsk (Russian Federation));Kalashnic, G.V. (All Russian Research and Scientific Inst. of Inorganic Materials, Moscow (Russian Federation))

Swelling and in-pile creep of neutron irradiated 15Cr15NiTi austenitic steels in the temperature range of 400 to 600 deg. C
Huebner, R.;Ehrlich, K. (Institut fuer Materialforschung, Forschungszentrum Karlsruhe, Karlsruhe (Germany))

In-pile strength of austenitic steels for fast reactors fuel pin cladding
Popov, V.V. (Institute of Physics and Power Engineering, State Scientific Center, Obninsk (Russian Federation))

A re-evaluation of helium/dpa and Hydrogen/dpa ratios for fast reactor and thermal reactor data used in fission-fusion correlations
Garner, F.A.;Greenwood, L.R. (Pacific Northwest National Lab., Richland, WA (United States))